Multipurpose neutron terminal

A multi-purpose, neutron technology, applied in the field of radiation protection, to achieve the effect of energy measurement performance evaluation and position-resolved evaluation, and various functions

Pending Publication Date: 2020-07-10
HARBIN ENG UNIV
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  • Summary
  • Abstract
  • Description
  • Claims
  • Application Information

AI Technical Summary

Problems solved by technology

[0006] At present, in the field of radiation protection, there is no terminal that can simultaneously perform the above multiple functions, and there is a lot of room for development of terminals that can realize the above multiple functions

Method used

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  • Multipurpose neutron terminal
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  • Multipurpose neutron terminal

Examples

Experimental program
Comparison scheme
Effect test

example 1

[0034] The arrangement scheme for generating beams that can be used for detector position resolution is as follows figure 2 , 3 and 4, the neutron source can be an Am-Be source. The source activity is 100mCi. There is a polyethylene disc with a diameter of about 25-30cm and a thickness of 40cm above it. The source is usually placed In a shielded well with a depth of about 1.31m and a platform with a certain depth relative to the ground, the equivalent dose rate close to the shielding material is about 0.9-1.0uSv / h. The slow down collimation system is a 90*90*70cm overall 3 The rectangular parallelepiped, which is partially hollowed out, includes the upper source and the collimation hole in the horizontal direction. The dimensions of each part are considered as follows: (1) Considering that the size of the source is a few centimeters, and the diameter of the polyethylene disc is about 25-30cm, choose L1=30cm, L2=10cm; (2) In order to support the polyethylene circle Disc, L3 is ...

example 2

[0037] The arrangement scheme for generating beams that can be used for the energy response of the detector is basically the same as in Example 1. The difference is that the diaphragm is replaced with a different moderating shield. The neutron beam passes through different moderators to get collimated beams of different energy intervals. By recording the number of times the detector responds to neutrons at different energies , The energy response curve of the detector can be obtained.

example 3

[0039] The layout scheme used to calibrate the neutron dose rate meter is as follows figure 1 , As shown in 2. First, transport the slow-down collimation system that is not needed in the calibration to a far enough position through orbit 1 to reduce the influence of scattering. Then the source is hoisted to a suitable height by controlling the elevator, and the inspected instrument can be transported to different distances from the source through the detection track 2 for measurement, and the total dose rate at different distances can be obtained. This dose rate includes the scattering neutron contribution. In order to eliminate the influence of the scattered beam, a shadow cone with proper geometry and position is placed between the source and the inspected instrument. Under this condition, the measured dose rate contributed by the scattered beam is obtained by subtracting the dose rate to obtain the main beam at different distances. The dose rate of the beam completes the c...

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Abstract

The invention relates to a multipurpose neutron terminal, which is mainly applied to dose calibration of a neutron dose rate instrument, material shielding performance and radiation detection in the field of radiation protection as well as energy measurement performance evaluation and position resolution evaluation of a neutron detector in the field of application. The multipurpose neutron terminal mainly comprises a neutron source, a control system and a collimation moderation system. The control system is used for hoisting the source to a proper height, and the multipurpose neutron terminalcan be used for instrument calibration with the application of a shadow cone. If the neutron source is matched with a movable collimation moderation system, a moderation shielding body can be freely replaced according to requirements, the neutron source can be perfectly embedded into the system, so that beams of the source cannot leak outwards, and neutron beams with different energy spectrums, different positions and different shapes can be obtained through using collimation holes. The multipurpose neutron terminal has the advantages of safety, stability, multiple functions, convenience, easiness in implementation and the like.

Description

Technical field [0001] The invention belongs to the field of radiation protection, and specifically relates to a multi-purpose neutron terminal. Background technique [0002] A neutron source is a device that can generate neutrons. It can be used for dose calibration of neutron dosimeters in the field of radiation protection, material shielding performance, radiation detection and energy measurement performance evaluation of neutron detectors in the application field, etc., in oil well logging , Moisture determination, activation analysis and other aspects have important applications, so the acquisition of different energy spectra of the neutron source is very important. The traditional neutron terminal can only achieve a single function, such as the calibration of a neutron dose rate meter or the measurement of the neutron energy spectrum distribution, and multiple terminals are often needed to achieve different functions. Under this background, a multi-purpose neutron terminal...

Claims

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Application Information

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Patent Type & Authority Applications(China)
IPC IPC(8): G01T7/00
CPCG01T7/005
Inventor 宋玉收赵云龙胡力元侯英伟刘辉兰吴坤
Owner HARBIN ENG UNIV
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